CA2818881C - Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement - Google Patents
Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement Download PDFInfo
- Publication number
- CA2818881C CA2818881C CA2818881A CA2818881A CA2818881C CA 2818881 C CA2818881 C CA 2818881C CA 2818881 A CA2818881 A CA 2818881A CA 2818881 A CA2818881 A CA 2818881A CA 2818881 C CA2818881 C CA 2818881C
- Authority
- CA
- Canada
- Prior art keywords
- break
- uncertainty
- values
- coolant accident
- loss
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000001228 spectrum Methods 0.000 title claims abstract description 36
- 238000000034 method Methods 0.000 title claims abstract description 29
- 238000004458 analytical method Methods 0.000 title claims abstract description 17
- 238000013210 evaluation model Methods 0.000 title claims description 27
- 239000002826 coolant Substances 0.000 claims abstract description 39
- 238000005070 sampling Methods 0.000 claims abstract description 14
- 238000013459 approach Methods 0.000 claims abstract description 8
- 238000013461 design Methods 0.000 claims description 12
- 238000004088 simulation Methods 0.000 claims description 11
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 9
- 238000000205 computational method Methods 0.000 claims description 6
- 230000004044 response Effects 0.000 claims description 6
- 238000012360 testing method Methods 0.000 claims description 6
- 238000012546 transfer Methods 0.000 claims description 6
- 230000001052 transient effect Effects 0.000 claims description 6
- 230000000694 effects Effects 0.000 claims description 5
- 230000003647 oxidation Effects 0.000 claims description 5
- 238000007254 oxidation reaction Methods 0.000 claims description 5
- 238000009472 formulation Methods 0.000 claims description 4
- 239000000203 mixture Substances 0.000 claims description 4
- 238000012805 post-processing Methods 0.000 claims description 4
- 230000001131 transforming effect Effects 0.000 claims description 2
- 230000008569 process Effects 0.000 abstract description 9
- 238000012109 statistical procedure Methods 0.000 abstract description 5
- 230000001105 regulatory effect Effects 0.000 abstract description 4
- 238000009826 distribution Methods 0.000 description 7
- 229920006395 saturated elastomer Polymers 0.000 description 5
- 238000012937 correction Methods 0.000 description 2
- 230000001186 cumulative effect Effects 0.000 description 2
- 238000009795 derivation Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000005315 distribution function Methods 0.000 description 2
- 238000012544 monitoring process Methods 0.000 description 2
- 238000013076 uncertainty analysis Methods 0.000 description 2
- 238000012614 Monte-Carlo sampling Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000284 extract Substances 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000001422 normality test Methods 0.000 description 1
- 238000011002 quantification Methods 0.000 description 1
- 230000035945 sensitivity Effects 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 230000005514 two-phase flow Effects 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
- 238000010200 validation analysis Methods 0.000 description 1
- 238000013022 venting Methods 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
La présente invention concerne un système et un procédé informatisés permettant d'effectuer une analyse de sûreté en prenant comme postulat un accident par défaut de refroidissement (LOCA) dans un réacteur nucléaire, pour une gamme complète de tailles de fracture, notamment des petites fractures, des fractures intermédiaires et des grandes fractures. En outre, la modélisation et l'analyse des accidents par défaut de refroidissement postulés dus à des petites fractures, des fractures intermédiaires et des grandes fractures sont effectuées avec un seul code informatique et un seul modèle d'entrée correctement validés par rapport à des données expérimentales pertinentes. Les incertitudes d'entrée et de modèle physique sont combinées selon un processus d'échantillonnage aléatoire, par exemple selon une approche de Monte Carlo direct (ASTRUM-FS) et des procédures statistiques avancées sont utilisées pour se conformer aux critères 10 CFR 50.46 de la commission de régulation nucléaire.
Applications Claiming Priority (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US41637110P | 2010-11-23 | 2010-11-23 | |
US61/416,371 | 2010-11-23 | ||
US13/303,188 US9208911B2 (en) | 2010-11-23 | 2011-11-23 | Full spectrum LOCA evaluation model and analysis methodology |
PCT/US2011/061987 WO2012071483A2 (fr) | 2010-11-23 | 2011-11-23 | Modèle d'évaluation complète et méthodologie d'analyse d'un accident par défaut de refroidissement |
US13/303,188 | 2011-11-23 |
Publications (2)
Publication Number | Publication Date |
---|---|
CA2818881A1 CA2818881A1 (fr) | 2012-05-31 |
CA2818881C true CA2818881C (fr) | 2019-06-11 |
Family
ID=46146413
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CA2818881A Active CA2818881C (fr) | 2010-11-23 | 2011-11-23 | Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement |
Country Status (5)
Country | Link |
---|---|
US (1) | US9208911B2 (fr) |
CN (1) | CN103548093B (fr) |
CA (1) | CA2818881C (fr) |
WO (1) | WO2012071483A2 (fr) |
ZA (1) | ZA201304378B (fr) |
Families Citing this family (20)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2014059057A1 (fr) | 2012-10-09 | 2014-04-17 | Avery Dennison Corporation | Adhésifs et procédés associés |
CN104462623A (zh) * | 2013-09-12 | 2015-03-25 | 中国核动力研究设计院 | 一种反应堆冷却剂系统loca分析模型快速建立方法 |
CN107207924B (zh) | 2015-02-05 | 2020-03-13 | 艾利丹尼森公司 | 恶劣环境用标签组件 |
US10990714B2 (en) | 2015-12-22 | 2021-04-27 | Bwxt Mpower, Inc. | Apparatus and method for safety analysis evaluation with data-driven workflow |
US10526511B2 (en) | 2016-12-22 | 2020-01-07 | Avery Dennison Corporation | Convertible pressure sensitive adhesives comprising urethane (meth)acrylate oligomers |
US11170073B2 (en) * | 2017-08-24 | 2021-11-09 | Westinghouse Electric Company Llc | Sequential embedding statistical analysis for multidimensional tolerance limits |
CN111125972B (zh) * | 2019-12-26 | 2021-10-19 | 西安交通大学 | 核电厂破口失水事故水力载荷分析方法 |
CN111144752B (zh) * | 2019-12-26 | 2022-04-05 | 西安交通大学 | 基于遗传算法的核电厂失水事故安注流量需求分析方法 |
CN111695762B (zh) * | 2020-04-29 | 2023-05-05 | 中国核电工程有限公司 | 核事故扩散结果的修正方法、装置及后果评价方法、系统 |
CN111554425B (zh) * | 2020-05-15 | 2022-02-11 | 中国核动力研究设计院 | 一种压水堆核电厂极小破口失水事故应对方法 |
CN113191425A (zh) * | 2021-04-28 | 2021-07-30 | 上海核工程研究设计院有限公司 | 一种泄漏点数据模型的建立方法、漏点识别方法、识别装置 |
CN113191556A (zh) * | 2021-05-08 | 2021-07-30 | 上海核工程研究设计院有限公司 | 一种核电Loca事件故障预测与诊断方法 |
CN113536537B (zh) * | 2021-06-10 | 2024-01-12 | 中国核动力研究设计院 | 一种大破口失水事故分析方法及系统 |
CN113948231B (zh) * | 2021-09-09 | 2023-08-08 | 国家电投集团科学技术研究院有限公司 | 核电厂小破口事故的关键现象的识别方法及装置 |
CN113761749B (zh) * | 2021-09-10 | 2022-03-22 | 哈尔滨工程大学 | 核反应堆概率安全裕度分析方法、系统、终端及存储介质 |
CN114638081B (zh) * | 2021-11-11 | 2023-03-24 | 国家电投集团科学技术研究院有限公司 | 核电设计软件模型评估系统 |
CN115099040B (zh) * | 2022-06-29 | 2023-09-29 | 中国人民解放军91439部队 | 一种板状结构网格模型破口面积计算方法及系统 |
CN115048809B (zh) * | 2022-07-11 | 2023-08-29 | 中国核动力研究设计院 | 一种用于多物理多尺度耦合系统的不确定性量化方法 |
CN115266794B (zh) * | 2022-07-29 | 2024-06-04 | 中国核动力研究设计院 | 一种loca高温辐照后uo2气孔演变行为获取方法 |
CN116305837B (zh) * | 2023-02-16 | 2024-02-02 | 华中科技大学 | 一种突出比例分析的模块化不确定性量化评估方法及设备 |
Family Cites Families (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5009833A (en) * | 1989-01-11 | 1991-04-23 | Westinghouse Electric Corp. | Expert system for surveillance, diagnosis and prognosis of plant operation |
KR100681487B1 (ko) * | 2002-10-30 | 2007-02-09 | 한국전력공사 | 원자력발전소 안전해석을 위한 최적평가체계 |
US8873698B2 (en) | 2002-12-18 | 2014-10-28 | Global Nuclear Fuel—Americas, LLC | Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria |
DE10334580B3 (de) * | 2003-07-28 | 2005-03-17 | Framatome Anp Gmbh | Brennelement für einen Druckwasserkernreaktor |
US8109766B2 (en) * | 2003-10-03 | 2012-02-07 | Global Nuclear Fuel-Americas Llc | Method for predicted reactor simulation |
US7426458B2 (en) * | 2004-12-30 | 2008-09-16 | Global Nuclear Fuel - Americas, Llc | Nuclear reactor reload licensing analysis system and method |
RU2005116169A (ru) * | 2005-05-20 | 2006-11-27 | Вадим Игоревич Дунаев (RU) | Способ и система анализа и оценки безопасности технологического процесса |
US7860207B2 (en) * | 2006-11-28 | 2010-12-28 | The Invention Science Fund I, Llc | Method and system for providing fuel in a nuclear reactor |
US7685079B2 (en) | 2006-12-21 | 2010-03-23 | Global Nuclear Fuel - Americas, Llc | Methods for evaluating robustness of solutions to constraint problems |
US20080154638A1 (en) * | 2006-12-22 | 2008-06-26 | Coyle Carl M | Method and system for providing cross-systems services to developmentally disabled youth |
US9502145B2 (en) * | 2009-09-23 | 2016-11-22 | Terrapower, Llc | Nuclear reactor operation and simulation |
-
2011
- 2011-11-23 US US13/303,188 patent/US9208911B2/en active Active
- 2011-11-23 CN CN201180063849.8A patent/CN103548093B/zh active Active
- 2011-11-23 WO PCT/US2011/061987 patent/WO2012071483A2/fr active Application Filing
- 2011-11-23 CA CA2818881A patent/CA2818881C/fr active Active
-
2013
- 2013-06-13 ZA ZA2013/04378A patent/ZA201304378B/en unknown
Also Published As
Publication number | Publication date |
---|---|
ZA201304378B (en) | 2014-02-26 |
CN103548093A (zh) | 2014-01-29 |
US20120185222A1 (en) | 2012-07-19 |
CA2818881A1 (fr) | 2012-05-31 |
WO2012071483A2 (fr) | 2012-05-31 |
WO2012071483A3 (fr) | 2013-09-19 |
CN103548093B (zh) | 2016-08-10 |
US9208911B2 (en) | 2015-12-08 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CA2818881C (fr) | Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement | |
US7366273B2 (en) | Method of determining margins to operating limits for nuclear reactor operation | |
Alfonsi et al. | RAVEN and dynamic probabilistic risk assessment: Software overview | |
Gonzalez-Cadelo et al. | Analysis of cold leg LOCA with failed HPSI by means of integrated safety assessment methodology | |
Jankovsky et al. | Dynamic event tree analysis with the SAS4A/SASSYS-1 safety analysis code | |
Szilard et al. | Industry application emergency core cooling system cladding acceptance criteria early demonstration | |
EP2643781B1 (fr) | Modèle d'évaluation complète et méthodologie d'analyse d'un accident par défaut de refroidissement | |
Zhang et al. | Application of the BEPU safety analysis method to quantify margins in nuclear power plants | |
Sun et al. | An advanced probability safety margin analysis approach combined deterministic and probabilistic safety assessment | |
Frepoli et al. | 10 CFR 50.46 c rulemaking: A novel approach in restating the LOCA problem for PWRs | |
Saghafi et al. | Development and qualification of a thermal-hydraulic nodalization for modeling station blackout accident in PSB-VVER test facility | |
Mandelli et al. | Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit | |
Mendizábal et al. | Activities in Spain on the integration of probabilistic and deterministic safety analysis methods. Discussion on their applicability to DEC-A scenarios | |
Jeon et al. | Development of an optimal mitigation strategy by estimating the conditional core damage probability with time-dependent recovery actions | |
Sanchez-Saez et al. | Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE | |
Pantyushin et al. | Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT | |
Yoon et al. | A case study of time-dependent risk informed integrated safety assessment under complex accident sequences | |
Ćepin | Evolution of probabilistic safety assessment and its applications in nuclear power plants | |
Frepoli et al. | Westinghouse Experience in Licensing and Applying Best-Estimate LOCA Methodologies within the Industry: Past, Present and Future | |
Lee et al. | Application of Dynamic PSA Approach for Accident Sequence Precursor Analysis: Case Study for Steam Generator Tube Rupture | |
Mazurok et al. | Analysis of existing thermal-hydraulic analysis methodologies in the framework of resource extension of reactor pressure vessels | |
Mandelli et al. | Risk-Informed Analysis of Commercial Nuclear Reactors: the RISMC Approach and 10CFR50. 69 | |
JP2005283439A (ja) | 逃がし安全弁容量評価方法および逃がし安全弁容量評価プログラム | |
Zimmermann | Safety Margin Assessment (SM2A): Stimulation for Further Development of BEPU Approaches? | |
Mandelli et al. | Improved Sampling Algorithms in Risk Informed Safety Applications |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
EEER | Examination request |
Effective date: 20160907 |